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Title: FUEL ELEMENTS FOR THERMAL-FISSION NUCLEAR REACTORS

Abstract

Fuel elements for thermal-fission nuclear reactors are described. The fuel element is comprised of a core of alumina, a film of a metal of the class consisting of copper, silver, and nickel on the outer face of the core, and a coating of an oxide of a metal isotope of the class consisting of Un/sup 235/, U/ sup 233/, and Pu/sup 239/ on the metal f ilm.

Inventors:
Publication Date:
Research Org.:
Originating Research Org. not identified
OSTI Identifier:
4111738
Patent Number(s):
US 2967811
Assignee:
U.S. Atomic Energy Commission DTIE; NSA-15-008326
NSA Number:
NSA-15-008326
Resource Type:
Patent
Resource Relation:
Other Information: Orig. Receipt Date: 31-DEC-61
Country of Publication:
United States
Language:
English
Subject:
REACTOR TECHNOLOGY; ALUMINUM; COATING; COPPER; FILMS; FUEL ELEMENTS; METALS; NICKEL; PLUTONIUM 239; REACTORS; SILVER; URANIUM 233; URANIUM 235

Citation Formats

Flint, O. FUEL ELEMENTS FOR THERMAL-FISSION NUCLEAR REACTORS. United States: N. p., 1961. Web.
Flint, O. FUEL ELEMENTS FOR THERMAL-FISSION NUCLEAR REACTORS. United States.
Flint, O. Tue . "FUEL ELEMENTS FOR THERMAL-FISSION NUCLEAR REACTORS". United States. doi:.
@article{osti_4111738,
title = {FUEL ELEMENTS FOR THERMAL-FISSION NUCLEAR REACTORS},
author = {Flint, O.},
abstractNote = {Fuel elements for thermal-fission nuclear reactors are described. The fuel element is comprised of a core of alumina, a film of a metal of the class consisting of copper, silver, and nickel on the outer face of the core, and a coating of an oxide of a metal isotope of the class consisting of Un/sup 235/, U/ sup 233/, and Pu/sup 239/ on the metal f ilm.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Tue Jan 10 00:00:00 EST 1961},
month = {Tue Jan 10 00:00:00 EST 1961}
}
  • Reactor fuel spheres suitable for use in thermal reactors such as those described in Patent Serial No. 848,901 may be fabricated comprising a moderator core, an electrically conducting outer face, and a coating of fissile material. The core may be made from beryllia, magnesia, and aluminia, while the outer face may be graphite or a metal, e.g., copper, silver, or nickel. Four examples of preferred fabrication in the above way are included. (D.L.C.)
  • A dispersion-type fuel material is described. Elements made of this material consist of a BeO or graphite shell enclosing an extruded body of UC, graphite, and organic binder. The UC particles are smaller in diameter than the fission fragment range. This fuel element is easily processed by grinding and sifting to remove moderator-filler which contains fission fragments. (T.R.H.)
  • A reactor fuel element is described which has a good thermal conductivity, high fuel density, dimensional stability with respect to temperature and radiation effects, and good corrosion resistance to water. The fuel element comprises a shaped piece of UC, PuC, ThC, or a mixture thereof, a protective can, and a thin protective layer between the can and the shaped piece. The protective layer may be a U silicide, a carbide or silicide of one of the elements of the Periodic System Groups IV to VI except Hf and Ta, a metal, or successive layers thereof. (D.L.C.)
  • Thermal exchange between fuel elements and the surrounding fluid is improved by fitting the fuel element casing with transverse fins over which a cover with inlet and outlet orifices (some having inclined blades) is placed. (D.C.W.)
  • A method is outlined for measuring the amount of fissile material in irradiated reactor fuel elements and other substarices. The method comprises irradiating the substance with thermal neutrons from an antimony-124-beryllium source, and measuring the fast neutrons produced by the fission. An apparatus for carrying out the method with fission chambers is described. (D.L.C.)